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Category:Letter
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[Table view] Category:Licensee Event Report (LER)
MONTHYEARNL-20-0230, Edwin I. Hatch Nuclear Plant, Unit 2, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La)2020-03-0202 March 2020 Edwin I. Hatch Nuclear Plant, Unit 2, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La) 05000366/LER-2020-0012020-03-0202 March 2020 LER 2020-001-00 for Edwin I. Hatch Nuclear Plant, Unit 2, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La) 05000321/LER-2017-0042017-08-24024 August 2017 Tornado Missile Vulnerabilities Result in Condition Prohibited by Technical Specifications, LER 17-004-00 for Edwin I. Hatch Regarding Safety Relief Valves' as Found Settings Resulted in Not Meeting Tech Spec Surveillance Criteria 05000366/LER-2017-0022017-04-13013 April 2017 Emergency Diesel Generator Start Due to Inadvertent Electrical Bus De-Energization, LER 17-002-00 for Edwin I. Hatch, Unit 2, Regarding Emergency Diesel Generator Start Due to Inadvertent Electrical Bus De-Energization 05000366/LER-2017-0032017-04-13013 April 2017 LER 17-003-00 for Edwin I. Hatch, Unit 2, Regarding Primary Containment Isolation Penetration Exceeded Overall Allowable Technical Specification Leakage Limits 05000321/LER-2017-0022017-04-0707 April 2017 High Pressure Coolant Injection System Declared Inoperable Due to Degraded Inverter, LER 17-002-00 for Edwin I. Hatch, Unit 1, Regarding High Pressure Coolant Injection System Declared Inoperable Due to Degraded Inverter 05000366/LER-2016-0042017-01-0303 January 2017 Condition Prohibited by Technical Specifications Due to Inoperable PCIV, LER 16-004-00 for Edwin I. Hatch Nuclear Plant, Unit 2, Regarding Condition Prohibited by Technical Specifications Due to Inoperable PCIV 05000366/LER-2016-0022016-07-13013 July 2016 Group I Isolation Received During Turbine Testing, LER 16-002-00 for Edwin I. Hatch, Unit 2, Regarding Group 1 Isolation Received During Turbine Testing 05000366/LER-2016-0012016-06-0808 June 2016 2C EDG Fuel Oil Relief Valve Leakage Caused Train Inoperability, LER 16-001-00 for E.I. Hatch, Unit 2, Regarding 2C EDG Fuel Oil Relief Valve Leakage Caused Train Inoperability 05000321/LER-2016-0042016-05-26026 May 2016 Safety Relief Valves As Found Settings Resulted in Not Meeting Tech Spec Surveillance Criteria, LER 16-004-00 for Edwin I. Hatch Nuclear Plant Unit 1 RE: Safety Relief Valves as Found Settings Resulted in Not Meeting Tech Spec Surveillance Criteria 05000321/LER-2016-0032016-04-14014 April 2016 Reactor Coolant System Piping Has Unacceptable Weld Indication Discovered During Refueling Outage, LER 16-003-00 for E.I. Hatch, Unit 1, Regarding Reactor Coolant System Piping Has Unacceptable Weld Indication Discovered During Refueling Outage 05000321/LER-2016-0022016-04-11011 April 2016 Performance of Operations With the Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment, LER 16-002-00 for E.I Hatch, Unit 1, Regarding Performance of Operations With the Potential to Drain the Reactor Vessel (OPDRV) Without Secondary Containment 05000321/LER-2016-0012016-04-0808 April 2016 Performance of Fuel Movement with Inoperable Rod Position Indication System in Violation of Technical Specifications, LER 16-001-00 for Edwin I. Hatch, Unit 1, Regarding Performance of Fuel Movement With Inoperable Rod Position Indication System in Violation of Technical Specifications NL-08-1906, LER 08-S01-00, for Edwin I. Hatch, Failure to Report Arrest Results in Inappropriate Access to Protected and Vital Areas2008-12-19019 December 2008 LER 08-S01-00, for Edwin I. Hatch, Failure to Report Arrest Results in Inappropriate Access to Protected and Vital Areas ML1019404552008-05-0808 May 2008 Southern Nuclear Plant E. I. Hatch - Actions for Potential Groundwater Contamination Events NL-06-2726, LER 06-S01-00 for Edwin I. Hatch Nuclear Plant, Re Contract Employee Failure to Self-Disclose Material Information for Unescorted Access2006-12-0505 December 2006 LER 06-S01-00 for Edwin I. Hatch Nuclear Plant, Re Contract Employee Failure to Self-Disclose Material Information for Unescorted Access ML17252B4401976-04-15015 April 1976 LER 76-026-00 for Hatch, Unit 1 Regarding an Occurrence of Open Links in Panel H11-P601 Defeating the Starting of All RHR Pumps After They Had Been Stopped 2020-03-02
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3662020001R00 - NRC Website |
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A Southern Nuclear E. D. Dean Ill Vice President - Plant Hatch l'hulll dwin I Hld<h I IU:!X Hat'h l'arkw<ty 1\nnh llaxlcy, GA 1 1513
~ 12 517 ~xw 1ul 912 11\1\ 2077 fax MAR 0 2 2020 Docket Nos.: 50-366 NL-20-0230 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Unit 2 Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La)
Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 50.73 (a)(2)(i)(B). 10 CFA 50.73 (a)(2)(ii)(A), and 10 CFR 50.73 (a)(2)(v)(C). Southem Nuclear Operating Company hereby submits the enclosed Licensee Event Report.
This letter contains no NRC commitments. If you have any questions, please contact the Hatch Licensing Manager, Jimmy Collins at 912.537.2342 Respectfully submitted, r!lfl~
E. D. Dean Vice President - Hatch EDD/JEUSCM
Enclosure:
LEA 2020-001 -00 Cc: Regional Administrator, Region II NRR Project Manager- Hatch Senior Resident Inspector- Hatch RTYPE: CHA02.004
Edwin I. Hatch Nuclear Plant Unit 2 Licensee Event Report 2020-001-00 Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La)
Enclosure LER 2020-001-00
NRC FORM366 (04-2018)
U.S. NUCLEAR REGULATORY COMMISSION
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- 1. Facility Name 2. Docket Number 3.Page Edwin I. Hatch Nuclear Plant Unit 2 05000 366 1 OF 3
- 4. nue Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La)
- 5. Event Date 6. LER Number 7. Report Date B. Other Facilities Involved I I Sequontlal Rev oclllty Name Docket Number Month O.y Year Year Monll\ Day Year Numb.,. 05000 No.
Docket Number 3 :l.
Foclllty Nome 01 04 2020 2020 001 00 21111..() 05000
- 9. Operating Mode 11. This Report Is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply) 0 20.2201(b) 0 20.220J(a)(3)(1) 0 50 .73(a)(2)(ii)(A) 0 S0.73(a)(2}(Yiii)(A) 0 20.2201(d) 0 20.2203(a)(3)(ii)
D 50 73(a)(2)(ii)(B}
D 50.73(a)(2}(viij)(B) 1 D 20.2203(a)(1) 0 20.2203(a)(4)
D 50 73(a)I 2)(iii)
D 50.7J(a)(2)(1x)(A) 0 20.2203(a}(2)(i) 0 50.36(c)(1)(1)(A)
D sa.73(aJ(2)(iv)(A) D 50,73(a)(2)(x)
- 10. Power Level 0 20.2203(a)(2)(ii} 0 50.36(c)(1)(1 )(A) D 50,73(a](2)(v)(A) D 73.71(a)(4) 0 20.2203(a}(2)(ill) 0 50.36(c)(2)
D S0.73(a)(2)(v)(B) 0 73.71(a)(5) 0 20 220J(a)(2}(iv) D 50.46(8)(3)(11) 0 50,73(a)(2)(v)(C) 0 73.77(8)(1) 100 0 20 2203(a}(2)(v) D 50.73(a)(2)(1)(A) D 50.73(a)(2)(v)(D) 0 73.n(a)(2)(1)
D 20.2203(a)(2)(vi) IZ] 50.7J(a)(2)(i)(B)
D 50.73(a)(2)(vii) D 73.77(a)(2)(iQ D 50.73(a)(2)(i)(C)
D Other (Specify In Abstract below or In NRC Form 366A)
- 12. licensee Contact forthls LER licensee Contact Telephone Number (Include Area Code)
Jimmy Collins- Licensing Manager 912-537-2342 I I
- 13. Complete One Line for each Component Failure Described In this Report I I I I C.UIO Syatem Manutac1u~ Reportable to ICES Cauao Syalem Component Monulac1um Reportable to ICES X BB Cois"v""'
F130 y
- 14. Supplemental Report Expected Monllt Day Year
- 15. Expected 0
Submission Date v.. (If yes, complete 15. Elcpected Submission Date) [Z] No Abstract (Limit to 1400 spaces, I.e., approximately 14 single-spaced typewritten lines)
On January 4, 2020 at 1109 EST, with Unit 2 operating at 100% rated thermal power, it was determined that the maximum allowable primary containment leakage rate (La) as defined in 10CFR50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors", had been exceeded under postulated accident conditions .
Engineering troubleshooting efforts identified the degraded primary containment penetration and noted that leakage past two primary containment isolation valves (PCIVs) was causing La to be exceeded under postulated accident conditions. Additional valves downstream of the PCIVs were closed to retum primary containment back to operable status.
The cause of the PC IV failures is currently unknown and will be determined during valve disassembly during a planned outage.
At that time, the PCIVs will be repaired and returned to operable status.
NRC FORM 366 (04*2018)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150..0104 EXPIRES: 03/31/2020 (04-2019)
Estimated burden per respon~e Ill complr with this manda!oly colledion reque$t 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported LICENSEE EVENT REPORT (LER) lessons learned arv incorporated inlo 1he icensing proce$$ and fed bad< 1o lndu$1ry, Send comments regatding burden estima18 Ill lhe Information Setvlces Branch (T*2 F43), U. S Nudeilf RegWiory CONTINUATION SHEET Commission WeshingiOn, DC 20555-0001, or by &-mai to lnlocollects.Resource@nrc.gov and to lhe Oe$k Offocer, 011\ca ollnlonnation and Regulatory Allairs, NEOB-10202. (J15G-OIG4). Office ol Management ard Budge~ Washington. DC 20503. H a mean$ used 10 ~~~~ an InformatiOn (See NUREG-1022, R.3 for lnstrucUon and guidance for completing this form co8ectlon does not display a currenlfy valid OMB control number, lhe NRC may not conduct Of htto*ttwww,nrc,govtreadlng*rm/doc-collections/nuregs/staff/srl022/Q/\ $p0nsor, and a pe~n Is not required to respord IO, lhe lnlonnatiOn cotJection.
- 1. FACIUTY NAME 2. DOCKET NUMBER 3. LER NUMBER c:JYEAR SEQUENTlAL REV 1- 0 NUMBER NO.
05000-1 I L:J -I Edwin I. Hatch Nuclear Plant Unit 2 366 001 NARRAllVE EVENT DESCRIPTION On January 4, 2020, at 1109 EST, with Unit 2 operating at 100% rated thermal power, it was determined that the maximum allowable primary containment leakage rate (La) as specified in the Technical Specifications and defined in 10 CFR 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors", had been exceeded under postulated accident conditions.
Engineering troubleshooting efforts identified that leakage past the drywell ventilation penetration inboard and outboard isolation valves was causing La to be exceeded under postulated accident conditions. This represented a failure of the referenced penetration to maintain primary containment integrity. Compensatory measures were Implemented to close and deactivate isolation valves downstream of the Primary Containment Isolation valves (PCIVs) (ISV) to isolate the leaking penetration and return primary containment to operable status. The downstream valves are safety-related and constructed to ASME Section Ill Class 2 with satisfactory Local Leak Rate Tests (LLRTs).
Failed Components Information:
Master Parts List Number: 2T48F319 and 2T48F320 Manufacturer: Fisher Controls Company Model Number: Model 9220 Type: Isolation Valves This event is reportable per 10 CFR 50.73(a)(2)(ii)(A) due to one of the plant's principle safety barriers being seriously degraded. This event is also reportable per 10 CFR 50.73(a)(2)(v)(C) for an event or condition that could have prevented fulfillment of a safety function that is needed to control the release of radioactive material. This event has been classified as a Safety System Functional Failure under NEI 99-02. This event is also reportable per 10 CFR 50.73(a)(2)(i)(B) for a condition prohibited by Technical Specifications because primary containment was inoperable in excess of the allotted Limited Condition of Operation (LCO) timeframe.
EVENT CAUSE ANALYSIS The cause of the PC IV failures cannot be confirmed until valve disassembly. During a planned outage, the PCIVs will be repaired and returned to operable status.
ASSESSMENT OF SAFETY CONSEQUENCES There was no radioactive release to the public, so there were no actual safety consequences as a result of this event.
Upon identification of the excessive leakage rate, the operating crew responded correctly by isolating the leakage path.
The applicable Technical Specifications were properly entered. and required actions were taken within the specified completion time.
The leakage through the degraded primary containment penetration for the as-found condition was determined to exceed La under postulated accident conditions. However, the primary containment leakage rate was below the level required to significantly impact the Core Damage Frequency and Large Early Release Frequency and was of low safety consequence. Additionally, any leakage past the degraded PCIVs during an actual event would have been filtered through SBGT and released through the main stack at an elevated level.
NRC FORM 3661\ (04-2018}
Page 2 of 3
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150..0104 EXPIRES: 03/31/2020 (04-2018)
Estimated burden per response b comply 1\flh lhls mandatory c:olection request 80 hour9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.;. Reported lessons leill!led atelnoo!pOtaled Into lhe &censing process and led back to Industry. Send ccmmeniS
- ~~'\ ) ~ ~
LICENSEE EVENT REPORT (LER} regi1111ing burden estimate 10 lhe Information Services Branch (T-2 F43) U. S, Nudear RegulaiOry
..... CONTINUATION SHEET
~ ~ . ~* : Conmsslon, WaslllngiOn, OC 205SS.OOOI or by &-mal to lnbcolleds.Resouroe@M:.gov, and 10
' 'J'/ lhe Desk O!fcer, Office of lntormatlon and RegulaiOry Affair!. NEOB-10202. (JISG-()104), Ofli011 ol Managemenl end Budge~ Washing!on, OC 20503. H a means used to Impose an lnfonnatlon (See NUREG-1 022, R.3 for Instruction and guidance for complellng this form oolection does not dlsplay a Cllnentty valid OMB coni!OI number, the NRC may not oonducl or http*llwwu,nrc,goWreadlog-rmldoc-collecUons/ouregs/slaff/sr1 D22/r3D Sj)OIISOr, and a person Is not rtqtJited ID respond to, the fonnalion cotlecioll
- 1. FACIUTY NAME 2. DOCKET NUMBER 3. LER NUMBER Edwin I. Hatch Nuclear Plant Unit 2 05000-1 366 1::::1 YEAR SEQUENTIAL NUMBER REV NO.
I ~-1 001 1-~
NARRATIVE CORRECTIVE ACTIONS During an upcoming planned outage, the referenced PCIVs will be repaired and returned to operable status.
PREVIOUS SIMILAR ISSUES On February 7, 2017, with Unit 2 in a refueling outage, the same drywell ventilation penetration inboard isolation valve failed LLRT. On February 19, 2017, while still in the refueling outage, the same drywell ventilation penetration outboard isolation valve failed LLRT. This condition represented a failure of the associated penetration to maintain primary containment integrity due to both PCIVs In this penetration flow path exceeding La.
The cause of the PCIVs exceeding La was attributed to inadequate conditions related to the disc sealing ring that was found on both valves. Corrective actions included replacing the ring assemblies and adjusting the set screws on both PCIVs. A satisfactory LLRT was subsequently performed for both valves.
NRC FORM 366A (04-2018) Page 3 of 3